Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
7963676 | Journal of Nuclear Materials | 2016 | 7 Pages |
Abstract
Investigation of corrosion behavior of stainless steel served as one kind of structure materials exposed to liquid lithium (Li) is one of the keys to apply liquid Li as potential plasma facing materials (PFM) or blanket coolant in the fusion device. Corrosion experiments of 304 austenite stainless steel (304Â SS) were carried out in static liquid Li at 600Â K and up to1584Â h at high vacuum with pressure less than 4Â ÃÂ 10â4Â Pa. After exposure to liquid Li, it was found that the weight of 304Â SS slightly decreased with weight loss rate of 5.7Â ÃÂ 10â4Â g/m2/h and surface hardness increased by about 50Â HV. Lots of spinel-like grains and holes were observed on the surface of specimens measured by SEM. By further EDS, XRD and metallographic analyzing, it was confirmed that the main compositions of spinel-like grains were M23C6 carbides, and 304Â SS produced a non-uniform corrosion behavior by preferential grain boundary attack, possibly due to the easy formation of M23C6 carbides and/or formation of Li compound at grain boundaries.
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Authors
Xiancai Meng, Guizhong Zuo, Jun Ren, Wei Xu, Zhen Sun, Ming Huang, Wangyu Hu, Jiansheng Hu, Huiqiu Deng,